Adjusting rod control method and device, electronic equipment, nuclear power station system and medium

Abstract

The embodiment of the invention provides an adjusting rod control method and device, electronic equipment, a nuclear power station system and a medium, and belongs to the technical field of nuclear power station safety. The method comprises the following steps: acquiring target power of a reactor in response to the condition information of a nuclear power plant system as a load shedding condition; determining a secondary circuit load demand signal according to the target power and the initial correction factor; controlling the power adjusting rod to move according to the secondary loop load demand signal and the first initial position of the power adjusting rod; adjusting the initial correction factor according to the second initial position of the temperature adjusting rod to obtain a target correction factor; according to the target correction factor, the target power, the actually measured temperature of the first loop subsystem and the actually measured power of the reactor, controlling a temperature adjusting rod to move to a middle position; and the demineralized water is injected into a loop subsystem according to the middle position and a preset safety position until the temperature adjusting rod reaches the safety position. According to the embodiment of the invention, the safety of the nuclear power station under the load shedding condition is quickly improved.

Description

Technical Field

[0001] The present application relates to the field of nuclear power plant safety technology, and in particular to a regulating rod control method and device, electronic equipment, a nuclear power plant system and a medium. Background Art

[0002] Load shedding transient conditions refer to the situation where a nuclear power plant suddenly loses part or all of its power load during operation. This situation may cause xenon poisoning. At this time, the reactivity of the reactor can be controlled by adjusting the position of the temperature regulating rod and the power regulating rod in the nuclear reactor core. Under load shedding transient conditions, the power regulating rod is usually inserted into the reactor to reduce power. The rapid accumulation of xenon poisoning causes the temperature regulating rod to move out of the safe position range.

[0003] In the related art, the strategy of injecting desalted water into the primary circuit of the nuclear power plant is to continuously dilute or dilute boric acid in batches. However, the former may cause excessive dilution, causing the temperature adjustment rod to be too low, while the latter takes too long. Therefore, how to quickly improve the safety of nuclear power plants under load shedding conditions has become a technical problem that needs to be solved urgently. Summary of the invention

[0004] The main purpose of the embodiments of the present application is to propose a regulating rod control method and device, electronic equipment, nuclear power plant system and medium, aiming to quickly improve the safety of the nuclear power plant under load shedding conditions.

[0005] To achieve the above-mentioned purpose, a first aspect of an embodiment of the present application provides a regulating rod control method, which is applied to a nuclear power plant system, wherein the nuclear power plant system includes a power regulating rod, a temperature regulating rod, a primary circuit subsystem and a secondary circuit subsystem, wherein the primary circuit subsystem includes a reactor, and the power regulating rod and the temperature regulating rod are respectively inserted into the reactor; the method includes:

[0006] Acquiring operating condition information of the nuclear power plant system;

[0007] In response to the operating condition information being a load shedding operating condition, obtaining a target power of the reactor matching the load shedding operating condition;

[0008] Determining a secondary circuit load demand signal of the secondary circuit subsystem according to the target power and a preset initial correction factor;

[0009] According to the secondary circuit load demand signal and the first initial position of the power regulating rod in the reactor, controlling the power regulating rod to move so as to adjust the power of the reactor to the target power;

[0010] Acquiring a second initial position of the temperature regulating rod in the reactor, and numerically adjusting the initial correction factor according to the second initial position to obtain a target correction factor;

[0011] Controlling the temperature regulating rod to move to an intermediate position according to the target correction factor, the target power, the measured temperature of the primary circuit subsystem, and the measured power of the reactor;

[0012] The target amount of desalted water required to dilute the boric acid is calculated based on the middle position of the temperature regulating rod, the preset safety position and the preset initial boric acid concentration of the first-loop subsystem, and the desalted water of the target amount is injected into the first-loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the first-loop subsystem until the temperature regulating rod reaches the safety position.

[0013] In some embodiments, controlling the power regulating rod to move according to the secondary circuit load demand signal and the first initial position of the power regulating rod in the reactor to adjust the power of the reactor to the target power includes:

[0014] Determining a target position of the power regulating rod in the reactor according to the secondary circuit load demand signal;

[0015] determining a position error according to a first initial position of the power regulating rod currently in the reactor and the target position;

[0016] A first rod position adjustment signal is generated according to the position error to control the movement of the power adjustment rod according to the first rod position adjustment signal until the power adjustment rod reaches the target position to adjust the power of the reactor to the target power.

[0017] In some embodiments, controlling the temperature regulating rod to move to the middle position according to the target correction factor, the target power, the measured temperature of the primary circuit subsystem, and the measured power of the reactor includes:

[0018] Correcting the secondary circuit load demand signal according to the target correction factor and the target power, and determining the target temperature of the primary circuit subsystem according to the corrected secondary circuit load demand signal;

[0019] The temperature regulating rod is controlled to move to the middle position according to the measured temperature of the primary circuit subsystem, the target temperature of the primary circuit subsystem, the secondary circuit load demand signal and the measured power of the reactor.

[0020] In some embodiments, the correcting the secondary circuit load demand signal according to the target correction factor and the target power, and determining the target temperature of the primary circuit subsystem according to the corrected secondary circuit load demand signal, comprises:

[0021] Obtaining an intermediate load demand signal by superimposing the target power and the target correction factor;

[0022] Performing first-order filtering on the intermediate load demand signal to obtain a candidate load demand signal, and replacing the secondary circuit load demand signal with the candidate load demand signal;

[0023] The target temperature of the primary circuit subsystem is determined according to a preset load-temperature mapping relationship and the corrected secondary circuit load demand signal.

[0024] In some embodiments, controlling the temperature regulating rod to move to the middle position according to the measured temperature of the primary circuit subsystem, the target temperature of the primary circuit subsystem, the secondary circuit load demand signal and the measured power of the reactor comprises:

[0025] generating a power deviation signal based on the secondary circuit load demand signal and the measured power;

[0026] Performing differentiation processing on the power deviation signal to obtain a power mismatch feedforward signal;

[0027] generating a temperature deviation signal based on the measured temperature and a target temperature of the primary circuit subsystem;

[0028] Superimposing the temperature deviation signal and the power deviation signal to obtain a second rod position adjustment signal;

[0029] The temperature adjustment rod is controlled to move according to the second rod position adjustment signal until the temperature adjustment rod moves to the middle position.

[0030] In some embodiments, the method of calculating the target amount of desalted water required for diluting boric acid with desalted water according to the middle position of the temperature regulating rod, the preset safety position, and the preset initial boric acid concentration of the primary subsystem, and injecting the target amount of desalted water into the primary subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary subsystem until the temperature regulating rod reaches the safety position includes:

[0031] Calculating the target amount of deionized water required for diluting boric acid with deionized water according to the middle position of the temperature adjustment rod, the preset safety position and the preset initial boric acid concentration of the primary circuit subsystem;

[0032] Dividing the target desalted water volume required to dilute the boric acid with the desalted water into a plurality of sub-water volumes;

[0033] The desalted water of each sub-water volume is controlled to be injected into the primary subsystem according to a second preset time period, so as to adjust the position of the temperature regulating rod by diluting the boric acid in the primary subsystem in batches until the temperature regulating rod reaches the safe position.

[0034] In some embodiments, before calculating the target amount of desalted water required for diluting boric acid with desalted water according to the middle position of the temperature regulating rod, the preset safety position, and the preset initial boric acid concentration of the primary subsystem, injecting the target amount of desalted water into the primary subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary subsystem until the temperature regulating rod reaches the safety position, the method further includes:

[0035] Acquire a first preset position and a second preset position; wherein the first preset position is the maximum value of the preset safety adjustment band of the temperature adjustment rod, and the second preset position is the minimum value of the preset safety adjustment band of the temperature adjustment rod;

[0036] Obtaining the lower limit position of the temperature regulating rod in the reactor;

[0037] The safety position is determined according to the first preset position, the second preset position and the lower limit position, wherein the safety position is lower than the first preset position, and the safety position is higher than the second preset position, and the safety position is higher than the lower limit position.

[0038] In some embodiments, the step of obtaining a second initial position of the temperature regulating rod in the reactor and numerically adjusting the initial correction factor according to the second initial position to obtain a target correction factor includes:

[0039] Integrate and calculate the initial correction factor and the preset increment in a first preset time period to obtain a candidate correction factor;

[0040] If the second initial position remains unchanged or increases, then in the next first preset time period, the candidate correction factor and the preset increment are integrated and calculated to obtain an intermediate correction factor, and the candidate correction factor is replaced by the intermediate correction factor;

[0041] If the second initial position decreases, the candidate correction factor is used as the target correction factor.

[0042] In some embodiments, the primary circuit subsystem includes a plurality of thermal circuits; before controlling the temperature regulating rod to move to an intermediate position according to the target correction factor, the target power, the measured temperature of the primary circuit subsystem, and the measured power of the reactor, the measured temperature of the primary circuit subsystem is obtained by the following steps:

[0043] For each of the thermal circuits, obtaining an inlet temperature of the thermal circuit and an outlet temperature of the thermal circuit;

[0044] Performing mean calculation based on the inlet temperature and the outlet temperature to obtain an average temperature;

[0045] The average temperature is screened to obtain the measured temperature of the primary circuit subsystem.

[0046] To achieve the above-mentioned purpose, the second aspect of an embodiment of the present application proposes an electronic device, which includes a memory and a processor, wherein the memory stores a computer program, and when the processor executes the computer program, the method described in the first aspect is implemented.

[0047] To achieve the above-mentioned purpose, a third aspect of an embodiment of the present application provides a nuclear power plant system, the nuclear power plant system comprising:

[0048] The electronic device described in the second aspect above;

[0049] A power regulating rod, a temperature regulating rod, a primary circuit subsystem and a secondary circuit subsystem, wherein the primary circuit subsystem includes a reactor.

[0050] To achieve the above-mentioned purpose, a fourth aspect of an embodiment of the present application provides an adjusting rod control device, the device comprising:

[0051] An operating condition information acquisition module, used to acquire the operating condition information of the nuclear power plant system;

[0052] a target power acquisition module, configured to acquire a target power of the reactor matching the load shedding condition in response to the operating condition information being a load shedding condition;

[0053] A load demand signal acquisition module, used to determine the secondary circuit load demand signal of the secondary circuit subsystem according to the target power and a preset initial correction factor;

[0054] a first rod position control module, used for controlling the movement of the power regulating rod according to the secondary circuit load demand signal and the first initial position of the power regulating rod in the reactor to adjust the power of the reactor to the target power;

[0055] a correction factor adjustment module, used for obtaining a second initial position of the temperature adjustment rod in the reactor, and numerically adjusting the initial correction factor according to the second initial position to obtain a target correction factor;

[0056] a second rod position control module, used for controlling the temperature regulating rod to move to an intermediate position according to the target correction factor, the target power, the measured temperature of the primary circuit subsystem, and the measured power of the reactor;

[0057] The dilution adjustment module is used to calculate the target amount of desalted water required to dilute the boric acid based on the middle position of the temperature adjustment rod, the preset safety position and the preset initial boric acid concentration of the first-loop subsystem, and inject the desalted water of the target amount of desalted water into the first-loop subsystem to adjust the position of the temperature adjustment rod by diluting the boric acid in the first-loop subsystem until the temperature adjustment rod reaches the safety position.

[0058] To achieve the above-mentioned purpose, the fifth aspect of the embodiments of the present application proposes a computer-readable storage medium, wherein the computer-readable storage medium stores a computer program, and when the computer program is executed by a processor, the method described in the first aspect is implemented.

[0059] The control method and device of the regulating rod, the electronic device, the nuclear power plant system and the medium proposed in the present application first determine the working condition of the nuclear power plant system in real time, determine the target power corresponding to the load shedding working condition, use the target power and the initial correction factor to determine the secondary circuit load demand signal, and then accurately control the rod position through the secondary circuit load demand signal and the initial position of the power regulating rod, so as to ensure that the power of the reactor is quickly adjusted to the expected level and avoid the potential safety risks caused by excessive or too low power. Then, the initial correction factor is adjusted to modify the secondary circuit load demand, and then the rod position of the temperature regulating rod is adjusted. Due to the rapid accumulation of xenon poison under the load shedding working condition, the temperature regulating rod stays at the top of the reactor, and the operation of modifying the correction factor is simple and fast. Compared with the prior art of direct dilution, this embodiment can avoid the temperature regulating rod staying at the top of the reactor for a long time. Then, combined with the target correction factor, the measured temperature, and the measured power, the temperature regulating rod is moved to the middle position, and desalted water is injected according to the middle position and the preset safe position to dilute the boric acid, so as to ensure that the temperature regulating rod can reach the safe position smoothly. Compared with the prior art, which calculates the volume of desalted water to be diluted by predicting the trend of xenon toxicity, the present embodiment provides a method for calculating the volume of desalted water to be diluted based on the rod position and the boric acid concentration, and the result is more accurate. Therefore, the present embodiment can quickly improve the safety of nuclear power plants under load shedding conditions. BRIEF DESCRIPTION OF THE DRAWINGS

[0060] Figure 1is a flow chart of the regulating rod control method provided in an embodiment of the present application;

[0061] Figure 2 A schematic diagram of a structure of a nuclear power plant system provided in an embodiment of the present application;

[0062] Figure 3 yes Figure 1 Flow chart of step S104 in FIG.

[0063] Figure 4 yes Figure 3 Flow chart of step S105 in FIG.

[0064] Figure 5 is another flow chart of the regulating rod control method provided in an embodiment of the present application;

[0065] Figure 6 yes Figure 1 Flow chart of step S106 in FIG.

[0066] Figure 7 yes Figure 6 Flow chart of step S601 in FIG.

[0067] Figure 8 yes Figure 6 Flowchart of step S602 in FIG.

[0068] Fig. 9 yes Figure 1 Flow chart of step S107 in FIG.

[0069] Fig.10 is another flow chart of the regulating rod control method provided in an embodiment of the present application;

[0070] Fig.11 This is a curve diagram of the relationship between the position of the adjusting rod and time provided in an embodiment of the present application;

[0071] Fig.12 is a curve diagram of the relationship between a correction factor and time provided in an embodiment of the present application;

[0072] Fig.13 is a curve diagram of the relationship between dilution flow rate and time provided in an embodiment of the present application;

[0073] Fig.14 is a schematic structural diagram of an adjusting rod control device provided in an embodiment of the present application;

[0074] Fig.15 It is a schematic diagram of the hardware structure of the electronic device provided in the embodiment of the present application. DETAILED DESCRIPTION

[0075] In order to make the purpose, technical solution and advantages of the present application more clearly understood, the present application is further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application and are not used to limit the present application.

[0076] It should be noted that, although the functional modules are divided in the device schematic diagram and the logical order is shown in the flowchart, in some cases, the steps shown or described may be performed in a different order than the module division in the device or the order in the flowchart. The terms "first", "second", etc. in the specification, claims and the above drawings are used to distinguish similar objects, and are not necessarily used to describe a specific order or sequence.

[0077] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as those commonly understood by those skilled in the art to which this application belongs. The terms used herein are only for the purpose of describing the embodiments of this application and are not intended to limit this application.

[0078] First, some nouns involved in this application are analyzed:

[0079] Pressurized water reactor nuclear power plant: Pressurized water reactor nuclear power plant is mainly composed of nuclear steam supply system (i.e. primary circuit system), steam turbine generator system (i.e. secondary circuit system) and other auxiliary systems. Its working principle is as follows: the main pump sends high-pressure coolant into the reactor. After the coolant absorbs the heat energy released by nuclear fuel fission in the reactor, it passes through the steam generator and then transfers the heat to the secondary circuit to generate steam, and then enters the steam turbine to do work and drive the generator to generate electricity. The exhaust steam that has done work condenses into water in the condenser, and then is sent to the heater by the condensation feed water pump, and then sent back to the steam generator after reheating. This is the secondary circuit system.

[0080] Load shedding condition: In the embodiments of the present application, the load shedding condition of a nuclear power plant generally refers to a condition in which a nuclear power plant or other power plant suddenly loses part or all of its power load during operation.

[0081] Xenon poisoning: Xenon (135Xe) is the most powerful neutron absorber known. It acts like a "poison" that can slow down or stop a chain reaction. A reactor that runs at a constant power for a long time has a stable steady-state equilibrium concentration of xenon. However, when the reactor power is reduced, the concentration of xenon can increase to a level sufficient to shut down the reactor. The reactor cannot be restarted in this state. This shutdown caused by the xenon concentration and the difficulty in restarting is called xenon poisoning. The reactivity loss caused by the equilibrium xenon concentration is called equilibrium xenon poisoning.

[0082] Load shedding transient conditions refer to the situation where a nuclear power plant suddenly loses part or all of its power load during operation. This situation may cause xenon poisoning. At this time, the reactivity of the reactor can be controlled by adjusting the position of the temperature regulating rod and the power regulating rod in the nuclear reactor core. The temperature regulating rod and the power regulating rod are both made of absorbent materials (such as boron, cadmium, etc.). They can absorb neutrons in the nuclear reactor, thereby adjusting the rate of nuclear fission reactions, and then adjusting the power and temperature of the reactor. The deeper the insertion into the core, the more neutrons are absorbed, the fewer neutrons there are, the lower the reaction rate, and the power and temperature of the reactor are also reduced.

[0083] Under load shedding transient conditions, the power regulating rod is usually inserted into the reactor to reduce power. The rapid accumulation of xenon poisoning causes the temperature regulating rod to leave the safe position range. In the related art, the strategy of injecting desalted water into the primary circuit of the nuclear power plant by continuous dilution or fractional dilution of boric acid is adopted to compensate for the negative reactivity introduced by xenon poisoning and balance the xenon poisoning. Boric acid (H 3 BO 3 ) is a neutron absorber commonly used in reactor coolants. It can absorb neutrons, thereby adjusting the reactivity of the reactor. The higher the concentration of boric acid, the more neutrons it absorbs, and the lower the reactivity of the reactor. The way to dilute boric acid is to inject demineralized water into the coolant of a loop to reduce the concentration of boric acid. Demineralized water does not contain neutron absorbing substances and will not absorb additional neutrons. When the concentration of boric acid decreases, the total amount of neutrons absorbed decreases, and more neutrons can participate in nuclear fission reactions, thereby improving the reactivity of the reactor.

[0084] Specifically, the changing trend of xenon poisoning during the load rejection transient is predicted based on the core operating status, and then the negative reactivity introduced by the xenon poisoning is calculated, and then the total volume of desalted water that needs to be diluted to balance this part of the negative reactivity is calculated. An existing solution is to inject the total volume of desalted water into the coolant at one time for continuous dilution, and observe the position of the temperature adjustment rod to the preset adjustment band. Since the reactivity introduced by the dilution generally takes 3 to 5 minutes to determine the effect, there is a large lag effect in its manifestation, and the xenon poisoning in the core cannot be accurately predicted, resulting in a certain deviation in the calculation of the dilution amount. Therefore, this solution is prone to excessive dilution, causing the temperature adjustment rod to be inserted below the lower limit, resulting in a Limiting Condition of Operation (LCO) event related to the technical specification, and the safety of the nuclear power plant cannot be guaranteed.

[0085] Another solution is to inject the total volume of desalted water in batches, wait for 3 to 5 minutes after each injection, and observe whether the position of the temperature regulating rod returns to the preset adjustment range. Although this solution can prevent over-dilution, the time required is significantly increased, and letting the temperature regulating rod stay on the top of the reactor for too long is not conducive to ensuring the safety of the nuclear power plant.

[0086] Therefore, how to quickly improve the safety of nuclear power plants under load shedding conditions has become a technical problem that needs to be solved urgently.

[0087] Based on this, the embodiments of the present application provide a regulating rod control method and device, electronic equipment, a nuclear power plant system and a medium, aiming to quickly improve the safety of a nuclear power plant under load shedding conditions.

[0088] The method and device, electronic device, and storage medium provided in the embodiments of the present application are specifically described through the following embodiments. First, the method in the embodiments of the present application is described.

[0089] The regulating rod control method provided in the embodiment of the present application relates to the field of nuclear power plant safety technology. The regulating rod control method provided in the embodiment of the present application can be applied to a terminal, can be applied to a server side, or can be software running in a terminal or a server side. In some embodiments, the terminal can be a smart phone, a tablet computer, a laptop computer, a desktop computer, etc.; the server side can be configured as an independent physical server, or a server cluster or distributed system composed of multiple physical servers, or a cloud server that provides basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communications, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application that implements the regulating rod control method, etc., but is not limited to the above forms.

[0090] The present application can be used in many general or special computer system environments or configurations. For example: personal computers, server computers, handheld or portable devices, tablet devices, multiprocessor systems, microprocessor-based systems, set-top boxes, programmable consumer electronics, network PCs, minicomputers, mainframe computers, distributed computing environments including any of the above systems or devices, etc. The present application can be described in the general context of computer-executable instructions executed by a computer, such as program modules. Generally, program modules include routines, programs, objects, components, data structures, etc. that perform specific tasks or implement specific abstract data types. The present application can also be practiced in distributed computing environments, in which tasks are performed by remote processing devices connected through a communication network. In a distributed computing environment, program modules can be located in local and remote computer storage media including storage devices.

[0091] Figure 1 is an optional flow chart of the regulating rod control method provided in the embodiment of the present application. Figure 1 The method is applied to a nuclear power plant system, and the method may include but is not limited to steps S101 to S107.

[0092] Step S101, obtaining operating information of a nuclear power plant system.

[0093] Step S102, in response to the operating condition information being a load shedding operating condition, obtaining a target power of the reactor matching the load shedding operating condition.

[0094] Step S103: determining a secondary circuit load demand signal of the secondary circuit subsystem according to the target power and a preset initial correction factor.

[0095] Step S104, according to the secondary circuit load demand signal and the first initial position of the power regulating rod in the reactor, controlling the power regulating rod to move so as to adjust the power of the reactor to the target power.

[0096] Step S105, obtaining a second initial position of the temperature regulating rod in the reactor, and numerically adjusting the initial correction factor according to the second initial position to obtain a target correction factor.

[0097] Step S106, controlling the temperature adjustment rod to move to the middle position according to the target correction factor, the target power, the measured temperature of the primary circuit subsystem, and the measured power of the reactor.

[0098] Step S107, calculate the target amount of desalted water required to dilute the boric acid based on the middle position of the temperature adjustment rod, the preset safety position and the preset initial boric acid concentration of the first-loop subsystem, and inject the desalted water of the target amount into the first-loop subsystem to adjust the position of the temperature adjustment rod by diluting the boric acid in the first-loop subsystem until the temperature adjustment rod reaches the safe position.

[0099] Steps S101 to S107 shown in the embodiment of the present application first determine the operating conditions of the nuclear power plant system in real time, determine the target power corresponding to the load shedding condition, use the target power and the initial correction factor to determine the secondary circuit load demand signal, and then accurately control the rod position through the secondary circuit load demand signal and the initial position of the power adjustment rod to ensure that the power of the reactor is quickly adjusted to the expected level and avoid potential safety risks caused by excessive or too low power. Then, the initial correction factor is adjusted to modify the secondary circuit load demand, and then the rod position of the temperature adjustment rod is adjusted. Due to the rapid accumulation of xenon poison under the load shedding condition, the temperature adjustment rod stays at the top of the reactor, and the operation of modifying the correction factor is simple and fast. Compared with the prior art of direct dilution, this embodiment can avoid the temperature adjustment rod staying at the top of the reactor for a long time. Then, combined with the target correction factor, the measured temperature, and the measured power, the temperature adjustment rod is moved to the middle position, and desalted water is injected according to the middle position and the preset safe position to dilute the boric acid to ensure that the temperature adjustment rod can reach the safe position smoothly. Compared with the prior art, which calculates the volume of desalted water to be diluted by predicting the trend of xenon toxicity, the present embodiment provides a method for calculating the volume of desalted water to be diluted based on the rod position and the boric acid concentration, and the result is more accurate. Therefore, the present embodiment can quickly improve the safety of nuclear power plants under load shedding conditions.

[0100] It should be noted that the regulating rod control method provided in the embodiment of the present application needs to be implemented based on the nuclear power plant system. Therefore, the nuclear power plant system provided in the embodiment of the present application is first introduced. Figure 2 , Figure 2 1 is a structural schematic diagram of a nuclear power plant system provided in an embodiment of the present application. The nuclear power plant system provided in an embodiment of the present application may be a pressurized water reactor nuclear power plant adopting a reactor-following mode, including a power regulating rod, a temperature regulating rod, a primary circuit subsystem and a secondary circuit subsystem, and an electronic device provided in an embodiment of the present application, which will be described in detail in subsequent related embodiments.

[0101] In the nuclear power plant system provided in the embodiment of the present application, the primary subsystem includes a reactor, and the regulating rod group includes a temperature regulating rod and a power regulating rod, which are inserted into the reactor. The function of the reactor is to carry out nuclear fission and convert nuclear energy into the heat energy of the coolant. The coolant is in liquid form, absorbs the heat energy generated by nuclear fission in the reactor, becomes a high-temperature and high-pressure liquid, and then enters the U-shaped tube of the steam generator along the pipeline, transfers the heat to the water on the outside of the U-shaped tube, and turns it into saturated steam. The cooled coolant is then pumped back into the reactor by the main pump for reheating, and this cycle is repeated to form a closed cycle of heat absorption and heat release. This circulation loop is the primary subsystem, also known as the nuclear steam supply system.

[0102] The water vapor generated by the steam generator enters the steam turbine and expands to do work, converting the heat energy into mechanical energy for the rotation of the turbine rotor. The turbine rotor and the generator rotor are rigidly connected, so the steam turbine directly drives the generator to generate electricity, converting mechanical energy into electrical energy. The steam that has done work is discharged into the condenser and cooled by circulating cooling water (such as seawater). The steam is condensed into water, and then it is input into the steam generator by the feed water pump. This circuit is the secondary circuit subsystem.

[0103] In step S101 of some embodiments, the operating condition information of the nuclear power plant can be a load shedding condition or a normal operating condition. When a steam turbine trip, load shedding, or power shedding occurs in a nuclear power plant, the nuclear power plant can be in a load shedding condition. When the nuclear power plant can operate normally as expected, for example, the reactor power and temperature are stable, the xenon concentration is in a balanced state, and the water pump can supply water normally, it can be determined that the nuclear power plant is in a normal operating condition.

[0104] In step S102 of some embodiments, in response to the operating condition information being a load shedding condition, the target power of the reactor matching the load shedding condition is obtained, and the target power refers to the power value expected to be achieved by the reactor. It should be noted that in some embodiments, when the nuclear power plant is in a normal operating condition, the final power setting value set by the nuclear power plant system is 0. When the nuclear power plant is in a load shedding condition, the final power setting value is set to be greater than the power of the turbine load, and the final power setting value is the above-mentioned target power. This is because when the nuclear power plant is in a load shedding condition, the turbine bypass system starts to operate, bypassing the high-temperature and high-pressure steam from the turbine and directly introducing it into the condenser or other cooling device, thereby avoiding steam from entering the turbine system. If the total load of the secondary circuit system is determined according to the turbine inlet pressure signal at this time, the load data will be deviated from the actual total load of the secondary circuit system. Therefore, setting a power setting value greater than the turbine load can allow the reactor to generate a power greater than the turbine load, and can quickly track when the turbine load increases, thereby improving the dynamic response capability of the system.

[0105] In step S103 of some embodiments, it can be understood that the maximum value is selected between the final power setting value and the turbine load as the basis for generating the secondary circuit load demand signal. When the operating condition information is a load rejection condition, the final power setting value is greater than the turbine load, and is superimposed as the target power of this embodiment and the preset initial correction factor, and the secondary circuit load demand signal of the secondary circuit subsystem is determined according to the superimposed result.

[0106] In other embodiments, when the operating condition information is a normal operating condition, the final power setting value is 0, and the turbine load reference value is obtained by selecting the maximum value, which is filtered and superimposed with a correction factor to obtain a secondary circuit load demand signal of the secondary circuit subsystem.

[0107] It is understood that the correction factor can be set manually.

[0108] In step S104 of some embodiments, please refer to Figure 3 In some embodiments, step S104 may include but is not limited to steps S301 to S303:

[0109] Step S301, determining the target position of the power regulating rod in the reactor according to the secondary circuit load demand signal.

[0110] Step S302, determining a position error according to a first initial position and a target position of the power regulating rod currently in the reactor.

[0111] Step S303, generating a first rod position adjustment signal according to the position error, and controlling the power adjustment rod to move according to the first rod position adjustment signal until the power adjustment rod reaches the target position, so as to adjust the power of the reactor to the target power.

[0112] In step S301 of some embodiments, the secondary circuit load demand signal can be calculated through a preset interpolation function to obtain the rod position expected to be reached by the power regulating rod in the reactor, that is, the target position. In the embodiment of the present application, the position of the regulating rod is usually expressed in steps, for example, the target position is 350.

[0113] In step S302 of some embodiments, the current position of the power regulating rod in the reactor is obtained, and the difference between the current position and the target position is calculated, and the obtained difference is the position error.

[0114] In step S303 of some embodiments, the first rod position adjustment signal is a control instruction for indicating how the power adjustment rod should move to eliminate the error, which may include an insertion / extraction signal and a movement speed signal. It is understandable that the insertion / extraction signal is determined based on the positive and negative values ​​of the position error to determine whether the power adjustment rod needs to be extracted or inserted, and the expected speed of the adjustment rod can be directly obtained based on the position error through the interpolation function, thereby determining the movement speed. The first rod position adjustment signal controls the motor or control rod drive mechanism (CRDM) of the power adjustment rod, so that the rod position of the power adjustment rod is gradually moved until the actual position of the power adjustment rod is consistent with the target position, which means that the position error is 0, which means that the power of the reactor at this time is the target power.

[0115] Steps S301 to S303 shown in the embodiment of the present application realize the automation of power regulation, improve the accuracy and real-time response capability of power regulation, and reduce manual intervention and operation errors. In addition, it can effectively avoid load fluctuations and system instability caused by delayed or inaccurate power output, and improve the stability and reliability of the nuclear reactor.

[0116] It should be noted that during the control process of the power regulating rod, due to the rapid accumulation of xenon poisoning, the temperature regulating rod will gradually rise to the top of the reactor. After the power regulating rod can stabilize at the above target position, the initial correction factor will be adjusted.

[0117] In step S105 of some embodiments, after completing the control of the power adjustment rod, the position of the temperature adjustment rod is obtained as the second initial position. Figure 4 In some embodiments, step S105 may include but is not limited to steps S401 to S403:

[0118] Step S401 : In a first preset time period, an initial correction factor and a preset increment are integrated and calculated to obtain a candidate correction factor.

[0119] Step S402: if the second initial position remains unchanged or increases, the candidate correction factor and the preset increment are integrated and calculated in the next first preset time period to obtain an intermediate correction factor, and the candidate correction factor is replaced by the intermediate correction factor.

[0120] Step S403: if the second initial position is lowered, the candidate correction factor is used as the target correction factor.

[0121] In step S401 of some embodiments, the first preset time period is a time period for adjusting the initial correction factor, which period may be 30 seconds. The preset increment is the amount of adjustment to the initial correction factor each time, which may be 20 megawatts. The specific values ​​of the first preset time period and the preset increment may be adjusted according to the actual nuclear power project, and the embodiments of the present application do not strictly limit this. The candidate correction factor is the adjusted initial correction factor, which is calculated by adding the initial correction factor to the preset increment. It should be noted that adding the initial correction factor will cause the power adjustment rod to rise. In order to prevent the position of the power adjustment rod from deviating too much, the adjustment of the correction factor is stopped once the temperature adjustment rod begins to drop.

[0122] In step S402 of some embodiments, if the second initial position remains unchanged or increases, the candidate correction factor is continuously superimposed, and the result obtained is the intermediate correction factor. Exemplarily, the initial correction factor is 0, the first preset time period is 30 seconds, and the preset increment is 20 megawatts (MW). When the time is 30 seconds, the candidate correction factor is 20MW, and the temperature adjustment rod does not drop. When it reaches 1 minute, the preset increment is continuously superimposed on the candidate correction factor, and the intermediate correction factor is 40MW, and this value is used as the new candidate correction factor.

[0123] In step S403 of some embodiments, if the temperature adjustment rod starts to drop, the candidate correction factor at this time is used as the target correction factor. In short, the correction factor is increased by a preset amount every first preset time period until the temperature adjustment rod starts to drop.

[0124] In the steps S401 to S403 shown in the embodiment of the present application, the degree of adjustment of the initial correction factor is determined by observing the position change of the temperature adjustment rod, ensuring that the most appropriate correction factor can be locked in time during operation, avoiding system instability caused by over-adjustment or under-adjustment, and improving the operating efficiency and safety of the nuclear power plant. The method of modifying the correction factor is simple and fast. Each adjustment only requires waiting for 30 seconds for the effect of the position of the temperature adjustment rod to be apparent. Compared with the existing solution technology, this can prevent the temperature adjustment rod from being on the top of the reactor for too long.

[0125] See also Figure 5 In some embodiments, before step S106, the primary circuit subsystem includes a plurality of thermal circuits, and the thermal circuits are used to flow coolant. The method provided in the embodiment of the present application also includes but is not limited to steps S501 to S503:

[0126] Step S501: for each thermal circuit, obtaining the inlet temperature and the outlet temperature of the thermal circuit.

[0127] Step S502, performing mean calculation based on the inlet temperature and the outlet temperature to obtain an average temperature.

[0128] Step S503, screening the average temperature to obtain the measured temperature of the primary circuit subsystem.

[0129] In step S501 of some embodiments, the inlet temperature of the thermal circuit is the temperature of the coolant when it enters the reactor core, and the outlet temperature of the thermal circuit is the temperature of the coolant when it flows out of the reactor core.

[0130] In step S502 of some embodiments, an average value is calculated based on the inlet temperature and the outlet temperature to obtain an average temperature. Since a primary circuit subsystem may be provided with multiple parallel thermal circuits, there may be multiple average temperatures.

[0131] In step S503 of some embodiments, the highest temperature among the multiple average temperatures is the measured temperature in this embodiment. In some embodiments, the signal containing the highest temperature value information is subjected to first-order filtering and lead / lag processing, and the processing result is transmitted as a signal containing the measured temperature.

[0132] Steps S501 to S503 shown in the embodiment of the present application can effectively capture the hottest area in the reactor by screening the highest value among multiple average temperatures as the actual measured temperature of the first-loop subsystem, and provide a reliable data for subsequent reactor temperature adjustment to ensure the safe operation of the reactor.

[0133] See also Figure 6 In some embodiments, step S106 may also include but is not limited to steps S601 to S602:

[0134] Step S601, correcting the secondary circuit load demand signal according to the target correction factor and the target power, and determining the target temperature of the primary circuit subsystem according to the corrected secondary circuit load demand signal.

[0135] Step S602, controlling the temperature regulating rod to move to the middle position according to the measured temperature of the primary circuit subsystem, the target temperature of the primary circuit subsystem, the secondary circuit load demand signal and the measured power of the reactor.

[0136] In step S601 of some embodiments, see Figure 7 Step S601 includes but is not limited to steps S701 to S703:

[0137] Step S701, obtaining an intermediate load demand signal by superimposing the target power and the target correction factor.

[0138] Step S702: Perform first-order filtering on the intermediate load demand signal to obtain a candidate load demand signal, and replace the secondary circuit load demand signal with the candidate load demand signal.

[0139] Step S703, determining the target temperature of the primary circuit subsystem according to the preset load-temperature mapping relationship and the corrected secondary circuit load demand signal.

[0140] In step S701 of some embodiments, the target power and the target correction factor are superimposed, and the obtained signal is the intermediate load demand signal.

[0141] In step S702 of some embodiments, the intermediate load demand signal may contain some unnecessary high-frequency components or noise, which may cause the system to be too sensitive to signal changes, resulting in an unstable or too drastic power adjustment process. The intermediate load demand signal is smoothed by first-order filtering to remove high-frequency noise, so that the processed candidate load demand signal is more stable, and the candidate load demand signal is used as a new secondary circuit load demand signal.

[0142] In step S703 of some embodiments, the preset load-temperature mapping relationship can be represented by a pre-determined interpolation function. The target temperature is the expected temperature of the reactor corresponding to the secondary circuit load demand signal. Substituting the secondary circuit load demand signal into the interpolation function can obtain the corresponding target temperature of the primary circuit subsystem.

[0143] In the steps S701 to S703 shown in the embodiment of the present application, by combining power demand with temperature regulation, the system can maintain the stability of the temperature in the reactor while meeting the load demand of the power grid, thereby ensuring the safe and efficient operation of the entire nuclear power plant. The technical effect of this series of steps is to ensure that the system can accurately control power and temperature under complex operating conditions while optimizing responsiveness and safety.

[0144] In step S602 of some embodiments, see Figure 8 Step S602 may include but is not limited to steps S801 to S805:

[0145] Step S801: generating a power deviation signal based on a secondary circuit load demand signal and the measured power.

[0146] Step S802: performing differentiation processing on the power deviation signal to obtain a power mismatch feedforward signal.

[0147] Step S803: generating a power deviation signal based on the secondary circuit load demand signal and the measured power.

[0148] Step S804: superimpose the temperature deviation signal and the power deviation signal to obtain a second rod position adjustment signal.

[0149] Step S805, controlling the temperature adjustment rod to move according to the second rod position adjustment signal until the temperature adjustment rod moves to the middle position.

[0150] In step S801 of some embodiments, the measured power is the power of the reactor, and the difference between the secondary circuit load demand signal and the measured power is calculated to obtain a power deviation. The signal reflecting the power deviation information is the power deviation signal.

[0151] In step S802 of some embodiments, the power deviation signal is subjected to inertial differentiation processing, and the signal result obtained is a power mismatch feedforward signal. It can be understood that power mismatch refers to the situation where there is a deviation between the measured power and the load demand. The power mismatch feedforward signal reflects the dynamic change rate of the power mismatch, and can predict future power demand changes in advance and adjust the system accordingly, which can significantly reduce the hysteresis reaction.

[0152] In step S803 of some embodiments, the difference between the measured temperature and the target temperature is calculated, the difference obtained is the temperature deviation, and the signal reflecting the temperature deviation is the temperature deviation signal.

[0153] In step S804 of some embodiments, the second rod position adjustment signal is used to indicate a control instruction on how the temperature adjustment rod should be moved to eliminate the temperature deviation, and it may include an insertion / extraction signal and a movement speed signal.

[0154] In step S805 of some embodiments, it is understandable that the expected speed of the temperature regulating rod can be directly obtained according to the temperature deviation and the power mismatch feedforward signal through the pre-determined interpolation function, thereby determining the movement speed.

[0155] It is understandable that the adjusted correction factor causes the secondary circuit load demand signal to change, which in turn affects the position of the temperature regulating rod. When the target correction factor is obtained, the temperature regulating rod begins to descend from the top of the reactor, and the position of the temperature regulating rod after stabilization is the middle position.

[0156] Steps S801 to S805 shown in the embodiment of the present application achieve efficient and precise control of the temperature regulating rod of the nuclear power plant by combining multi-dimensional signal processing with feedback control.

[0157] Steps S601 to S602 shown in the embodiment of the present application coordinate the dual feedback signals of power and temperature to ensure that the temperature regulation function of the nuclear reactor can respond quickly while meeting the load demand.

[0158] In step S107 of some embodiments, see Fig. 9 In some embodiments, step S107 may include but is not limited to steps S901 to S903:

[0159] Step S901, calculating the target amount of desalted water required for diluting boric acid based on the middle position of the temperature adjustment rod, the preset safety position and the preset initial boric acid concentration of the primary circuit subsystem.

[0160] Step S902, dividing the target desalted water volume required for diluting boric acid with desalted water into a plurality of sub-water volumes.

[0161] Step S903, controlling the injection of desalted water of each sub-water volume into the primary sub-system according to the second preset time period, so as to adjust the position of the temperature regulating rod by diluting the boric acid in the primary sub-system in batches until the temperature regulating rod reaches a safe position.

[0162] In step S901 of some embodiments, the coolant in the primary subsystem includes a certain concentration of boric acid. Dilution of the boric acid concentration can improve the reactivity of the reactor, thereby balancing the xenon poisoning. The boric acid concentration before the dilution action is performed is the preset initial boric acid concentration. At this time, the volume of demineralized water required for the temperature regulating rod to reach the safe position from the middle position is calculated. Specifically, the change in reactivity caused by the temperature regulating rod from the middle position to the safe position is determined. The change in reactivity caused by the change in xenon poisoning in this process should also be considered. Then, the change in boric acid concentration is determined based on the change in reactivity. Then, the target demineralized water volume is calculated based on the change in boric acid concentration, the initial boric acid concentration, and the total volume of the coolant in the primary circuit, that is, the volume of demineralized water required for the dilution action.

[0163] In step S902 of some embodiments, the desalted water is then diluted in batches, and the dilution requirement can be divided equally or split into different data amounts, so that the amount of early dilution is greater than the amount of late dilution, and the data after the dilution requirement is split is the sub-water amount. In this embodiment, the dilution requirement is divided into four equal parts to obtain the sub-water amounts.

[0164] In step S903 of some embodiments, the second preset time period is a time period for waiting for the position of the temperature adjustment rod to be manifested, and its duration may be 3 to 5 minutes, which is not strictly limited in this embodiment. Deionized water having a volume of sub-water is injected into the primary circuit subsystem every second preset time period, and the temperature adjustment rod is gradually controlled to a safe position.

[0165] Steps S901 to S903 shown in the embodiment of the present application achieve precise adjustment of the temperature adjustment rod position and reactor reactivity through accurate volume calculation, fractional injection and time control, thereby ensuring safe and efficient operation of the nuclear power plant under load changes and xenon toxicity effects.

[0166] In some embodiments, see Fig.10 Before step S106, the control method for adjusting the rod provided in the embodiment of the present application can also obtain the safe position through steps S1001 to S1003:

[0167] Step S1001, obtaining a first preset position and a second preset position.

[0168] Step S1002, obtaining the lower limit position of the temperature regulating rod in the reactor.

[0169] Step S1003, determining a safe position according to the first preset position, the second preset position and the lower limit position.

[0170] In step S1001 of some embodiments, the first preset position is the maximum value of the preset safety adjustment band of the temperature adjustment rod, and the second preset position is the minimum value of the preset safety adjustment band of the temperature adjustment rod. The position range of the temperature adjustment rod that can ensure safe operation in the reactor of the nuclear power plant is the preset safety adjustment band. This position range can be designed according to different nuclear power plants, and this embodiment does not strictly limit its specific data.

[0171] In step S1002 of some embodiments, the low limit position refers to the position of the temperature regulating rod in the nuclear power plant that has dropped below the minimum allowable limit of operation. It is understandable that if the position of the regulating rod reaches the minimum allowable limit, it will trigger the occurrence of the LCO event, thereby affecting the safety of the nuclear power plant.

[0172] In step S1003 of some embodiments, it is understood that the safety position is lower than the first preset position, and the safety position is higher than the second preset position, and the safety position is higher than the lower limit position. The safety position is the position that the temperature adjustment rod is expected to reach, and usually the middle value between the first preset position and the second preset position is used as the safety position.

[0173] Steps S1001 to S1003 shown in the embodiment of the present application accurately determine the safe position of the temperature adjustment rod, thereby improving the operating safety and control accuracy of the nuclear power plant reactor.

[0174] Next, the following specific embodiments will introduce the control method of the regulating rod under the load rejection condition. Fig.11 , Fig.12 and Fig.13 , Fig.11 To adjust the relationship between the stick position and time, Fig.12 is the relationship curve between the correction factor and time, Fig.13 is the relationship curve between dilution flow and time, Fig.11 , Fig.12 and Fig.13 The time axis corresponds to Fig.11 In the figure, the blue line reflects the actual position of the temperature adjustment rod (R rod), the red line reflects the actual position of the power adjustment rod (G rod), and the green line reflects the required position of the power adjustment rod (G rod).

[0175] Exemplarily, the 100% full power (FP) platform steam turbine of the nuclear power plant trips, and the nuclear power plant operating condition suddenly changes to a load shedding condition. In response to the load shedding condition, a final power setting value of 30% FP, that is, the target power, is generated. The target position of the G rod suddenly changes from 615 steps to 350 steps, and the G rod is controlled to be gradually inserted into the core until the target position. While responding to the load shedding condition, the primary circuit system overheats in the early stage of the load shedding transient, so that the measured temperature is greater than the temperature reference value, forming a temperature deviation. In addition, the load of the secondary circuit subsystem suddenly drops, resulting in the output of the power mismatch feedforward signal. Under the joint action of the two, a large negative comprehensive temperature deviation signal is formed, resulting in the R rod being inserted into the core from step 197 to step 115. During the period AC when the G rod is gradually inserted into the core, as the G rod is inserted, the power of the primary circuit is gradually reduced, the power mismatch feedforward signal changes from positive to negative, and the comprehensive temperature deviation changes from negative to positive. The R rod is gradually lifted in the period AB and finally raised to the top position of the reactor 225 steps. At this time, due to the drastic change in the core power, the xenon poison gradually accumulates, resulting in an overcooling trend in the primary circuit, and the R rod is maintained at the top of the reactor for a long time. When the G rod reaches the target position, wait for a period of time, determine that the G rod position is stable in the period CD, and start to increase the correction factor hour by hour. Fig.12 The relationship between the value of the correction factor and time is described in the figure. The initial correction factor is 0. Every time the correction factor accumulates 20 MW, each increase will cause the G rod to rise by 5 steps. When the correction factor is increased to 60MW, the G rod rises to 365 steps, and the R rod begins to drop from 225 steps, reaching 210 steps at time E. Wait for 1 to 2 minutes (time period EF) to observe the stability of the R rod position. At this time, it can be determined that the middle position of the R rod is 210 steps. From time F, the first circuit is diluted in batches, and the dilution flow rate is set to 25 cubic meters per hour. After the first dilution is completed, the R rod drops and waits for the R rod to stabilize (time G), and its position is determined to be 198 steps. Perform another dilution operation, and the R rod drops to 186 steps. If the R rod has not reached the expected position, continue to dilute until the R rod returns to the middle of the adjustment band.

[0176] See also Fig.14 The embodiment of the present application further provides a regulating rod control device, which can implement the above regulating rod control method, and the device includes:

[0177] The operating condition information acquisition module is used to obtain the operating condition information of the nuclear power plant system;

[0178] A target power acquisition module, used for acquiring a target power of the reactor matching the load shedding condition in response to the operating condition information being a load shedding condition;

[0179] A load demand signal acquisition module, used to determine a secondary circuit load demand signal of the secondary circuit subsystem according to a target power and a preset initial correction factor;

[0180] A first rod position control module, used for controlling the movement of the power regulating rod according to the secondary circuit load demand signal and the first initial position of the power regulating rod in the reactor to adjust the power of the reactor to the target power;

[0181] A correction factor adjustment module, used for obtaining a second initial position of the temperature adjustment rod in the reactor, and numerically adjusting the initial correction factor according to the second initial position to obtain a target correction factor;

[0182] A second rod position control module is used to control the temperature adjustment rod to move to an intermediate position according to a target correction factor, a target power, a measured temperature of a primary circuit subsystem, and a measured power of the reactor;

[0183] The dilution adjustment module is used to calculate the target amount of desalted water required to dilute the boric acid based on the middle position of the temperature adjustment rod, the preset safety position and the preset initial boric acid concentration of the primary subsystem, and inject the desalted water of the target amount of desalted water into the primary subsystem to adjust the position of the temperature adjustment rod by diluting the boric acid in the primary subsystem until the temperature adjustment rod reaches the safe position.

[0184] The specific implementation of the regulating rod control device is basically the same as the specific implementation of the regulating rod control method described above, and will not be repeated here.

[0185] The embodiment of the present application also provides an electronic device, the electronic device includes a memory and a processor, the memory stores a computer program, and the processor implements the above-mentioned adjustment stick control method when executing the computer program. The electronic device can be any intelligent terminal including a tablet computer, a car computer, etc.

[0186] See also Fig.15 , Fig.15 The hardware structure of an electronic device of another embodiment is illustrated, and the electronic device includes:

[0187] The processor 1501 may be implemented by a general-purpose CPU (Central Processing Unit), a microprocessor, an application-specific integrated circuit (ASIC), or one or more integrated circuits, and is used to execute relevant programs to implement the technical solutions provided in the embodiments of the present application;

[0188] The memory 1502 can be implemented in the form of a read-only memory (ROM), a static storage device, a dynamic storage device, or a random access memory (RAM). The memory 1502 can store an operating system and other application programs. When the technical solution provided in the embodiment of this specification is implemented by software or firmware, the relevant program code is stored in the memory 1502, and the processor 1501 calls and executes the control method of the regulating rod in the embodiment of this application;

[0189] Input / output interface 1503, used to implement information input and output;

[0190] Communication interface 1504, used to realize communication interaction between the device and other devices, which can be realized through wired mode (such as USB, network cable, etc.) or wireless mode (such as mobile network, WIFI, Bluetooth, etc.);

[0191] A bus 1505 that transmits information between the various components of the device (e.g., the processor 1501, the memory 1502, the input / output interface 1503, and the communication interface 1504);

[0192] The processor 1501 , the memory 1502 , the input / output interface 1503 and the communication interface 1504 are connected to each other in communication within the device via the bus 1505 .

[0193] An embodiment of the present application further provides a computer-readable storage medium, which stores a computer program. When the computer program is executed by a processor, the above-mentioned adjustment rod control method is implemented.

[0194] The memory, as a non-transient computer-readable storage medium, can be used to store non-transient software programs and non-transient computer executable programs. In addition, the memory may include a high-speed random access memory, and may also include a non-transient memory, such as at least one disk storage device, a flash memory device, or other non-transient solid-state storage device. In some embodiments, the memory may optionally include a memory remotely disposed relative to the processor, and these remote memories may be connected to the processor via a network. Examples of the above-mentioned network include, but are not limited to, the Internet, an intranet, a local area network, a mobile communication network, and combinations thereof.

[0195] The control method, control device, electronic device and storage medium provided by the embodiment of the present application first determine the working condition of the nuclear power plant system in real time, determine the target power corresponding to the load shedding working condition, use the target power and the initial correction factor to determine the secondary circuit load demand signal, and then accurately control the rod position through the secondary circuit load demand signal and the initial position of the power regulating rod, so as to ensure that the power of the reactor is quickly adjusted to the expected level and avoid the potential safety risks caused by excessive or too low power. Then, the initial correction factor is adjusted to modify the secondary circuit load demand, and then the rod position of the temperature regulating rod is adjusted. Due to the rapid accumulation of xenon poison under the load shedding working condition, the temperature regulating rod stays at the top of the reactor, and the operation of modifying the correction factor is simple and fast. Compared with the prior art of direct dilution, this embodiment can avoid the temperature regulating rod staying at the top of the reactor for a long time. Then, combined with the target correction factor, the measured temperature, and the measured power, the temperature regulating rod is moved to the middle position, and deionized water is injected according to the middle position and the preset safe position to dilute the boric acid, so as to ensure that the temperature regulating rod can reach the safe position smoothly. Compared with the prior art, which calculates the volume of desalted water to be diluted by predicting the trend of xenon toxicity, the present embodiment provides a method for calculating the volume of desalted water to be diluted based on the rod position and the boric acid concentration, and the result is more accurate. Therefore, the present embodiment can quickly improve the safety of nuclear power plants under load shedding conditions.

[0196] The embodiments described in the embodiments of the present application are intended to more clearly illustrate the technical solutions of the embodiments of the present application and do not constitute a limitation on the technical solutions provided in the embodiments of the present application. Those skilled in the art will appreciate that with the evolution of technology and the emergence of new application scenarios, the technical solutions provided in the embodiments of the present application are also applicable to similar technical problems.

[0197] Those skilled in the art will appreciate that the technical solutions shown in the figures do not constitute a limitation on the embodiments of the present application, and may include more or fewer steps than shown in the figures, or a combination of certain steps, or different steps.

[0198] The device embodiments described above are merely illustrative, and the units described as separate components may or may not be physically separated, that is, they may be located in one place or distributed on multiple network units. Some or all of the modules may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0199] Those skilled in the art will appreciate that all or some of the steps in the methods disclosed above, and the functional modules / units in the systems and devices may be implemented as software, firmware, hardware, or a suitable combination thereof.

[0200] The terms "first", "second", "third", "fourth", etc. (if any) in the specification of the present application and the above-mentioned drawings are used to distinguish similar objects, and are not necessarily used to describe a specific order or sequence. It should be understood that the data used in this way can be interchangeable where appropriate, so that the embodiments of the present application described herein can be implemented in an order other than those illustrated or described herein. In addition, the terms "including" and "having" and any of their variations are intended to cover non-exclusive inclusions, for example, a process, method, system, product or device comprising a series of steps or units is not necessarily limited to those steps or units clearly listed, but may include other steps or units that are not clearly listed or inherent to these processes, methods, products or devices.

[0201] It should be understood that in the present application, "at least one (item)" means one or more, and "plurality" means two or more. "And / or" is used to describe the association relationship of associated objects, indicating that three relationships may exist. For example, "A and / or B" can mean: only A exists, only B exists, and A and B exist at the same time, where A and B can be singular or plural. The character " / " generally indicates that the objects associated before and after are in an "or" relationship. "At least one of the following" or similar expressions refers to any combination of these items, including any combination of single or plural items. For example, at least one of a, b or c can mean: a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, c can be single or multiple.

[0202] In the several embodiments provided in the present application, it should be understood that the disclosed devices and methods can be implemented in other ways. For example, the device embodiments described above are only schematic. For example, the division of the above units is only a logical function division. There may be other division methods in actual implementation, such as multiple units or components can be combined or integrated into another system, or some features can be ignored or not executed. Another point is that the mutual coupling or direct coupling or communication connection shown or discussed can be through some interfaces, indirect coupling or communication connection of devices or units, which can be electrical, mechanical or other forms.

[0203] The units described above as separate components may or may not be physically separated, and the components shown as units may or may not be physical units, that is, they may be located in one place or distributed on multiple network units. Some or all of the units may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0204] In addition, each functional unit in each embodiment of the present application may be integrated into one processing unit, or each unit may exist physically separately, or two or more units may be integrated into one unit. The above-mentioned integrated unit may be implemented in the form of hardware or in the form of software functional units.

[0205] If the integrated unit is implemented in the form of a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of the present application, or the part that contributes to the prior art, or all or part of the technical solution can be embodied in the form of a software product, and the computer software product is stored in a storage medium, including multiple instructions to enable a computer device (which can be a personal computer, server, or network device, etc.) to execute all or part of the steps of the methods of various embodiments of the present application. The aforementioned storage medium includes: U disk, mobile hard disk, read-only memory (Read-Only Memory, referred to as ROM), random access memory (Random Access Memory, referred to as RAM), disk or optical disk and other media that can store programs.

[0206] The preferred embodiments of the present invention are described above with reference to the accompanying drawings, but the scope of the rights of the present invention is not limited thereto. Any modification, equivalent substitution and improvement made by a person skilled in the art without departing from the scope and essence of the present invention should be within the scope of the rights of the present invention.

Claims

1. A control method for a regulating rod, characterized in that: Applied to a nuclear power plant system, the nuclear power plant system includes a power regulating rod, a temperature regulating rod, a primary circuit subsystem and a secondary circuit subsystem, the primary circuit subsystem includes a reactor, the power regulating rod and the temperature regulating rod are respectively inserted into the reactor; the method includes: Acquiring operating condition information of the nuclear power plant system; In response to the operating condition information being a load shedding operating condition, obtaining a target power of the reactor matching the load shedding operating condition; Determining a secondary circuit load demand signal of the secondary circuit subsystem according to the target power and a preset initial correction factor; According to the secondary circuit load demand signal and the first initial position of the power regulating rod in the reactor, controlling the power regulating rod to move so as to adjust the power of the reactor to the target power; Acquiring a second initial position of the temperature regulating rod in the reactor, and numerically adjusting the initial correction factor according to the second initial position to obtain a target correction factor; Controlling the temperature regulating rod to move to an intermediate position according to the target correction factor, the target power, the measured temperature of the primary circuit subsystem, and the measured power of the reactor; The target amount of desalted water required to dilute the boric acid is calculated based on the middle position of the temperature regulating rod, the preset safety position and the preset initial boric acid concentration of the first-loop subsystem, and the desalted water of the target amount is injected into the first-loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the first-loop subsystem until the temperature regulating rod reaches the safety position.

2. The method according to claim 1, characterized in that The controlling the power regulating rod to move according to the secondary circuit load demand signal and the first initial position of the power regulating rod in the reactor to adjust the power of the reactor to the target power includes: Determining a target position of the power regulating rod in the reactor according to the secondary circuit load demand signal; determining a position error according to a first initial position of the power regulating rod currently in the reactor and the target position; A first rod position adjustment signal is generated according to the position error, so as to control the movement of the power adjustment rod according to the first rod position adjustment signal until the power adjustment rod reaches the target position, so as to adjust the power of the reactor to the target power.

3. The method according to claim 1, characterized in that The step of controlling the temperature regulating rod to move to the middle position according to the target correction factor, the target power, the measured temperature of the primary circuit subsystem, and the measured power of the reactor comprises: Correcting the secondary circuit load demand signal according to the target correction factor and the target power, and determining the target temperature of the primary circuit subsystem according to the corrected secondary circuit load demand signal; The temperature regulating rod is controlled to move to the middle position according to the measured temperature of the primary circuit subsystem, the target temperature of the primary circuit subsystem, the secondary circuit load demand signal and the measured power of the reactor.

4. The method according to claim 3, characterized in that The step of correcting the secondary circuit load demand signal according to the target correction factor and the target power, and determining the target temperature of the primary circuit subsystem according to the corrected secondary circuit load demand signal comprises: Obtaining an intermediate load demand signal by superimposing the target power and the target correction factor; Performing first-order filtering on the intermediate load demand signal to obtain a candidate load demand signal, and replacing the secondary circuit load demand signal with the candidate load demand signal; The target temperature of the primary circuit subsystem is determined according to a preset load-temperature mapping relationship and the corrected secondary circuit load demand signal.

5. The method according to claim 3, characterized in that: The controlling the temperature regulating rod to move to the middle position according to the measured temperature of the primary circuit subsystem, the target temperature of the primary circuit subsystem, the secondary circuit load demand signal and the measured power of the reactor comprises: generating a power deviation signal based on the secondary circuit load demand signal and the measured power; Performing differentiation processing on the power deviation signal to obtain a power mismatch feedforward signal; generating a temperature deviation signal based on the measured temperature and a target temperature of the primary circuit subsystem; Superimposing the temperature deviation signal and the power deviation signal to obtain a second rod position adjustment signal; The temperature adjustment rod is controlled to move according to the second rod position adjustment signal until the temperature adjustment rod moves to the middle position.

6. The method according to claim 1, characterized in that The method comprises: calculating a target amount of desalted water required for diluting boric acid with desalted water according to the middle position of the temperature regulating rod, a preset safety position, and a preset initial boric acid concentration of the primary circuit subsystem, injecting the desalted water of the target amount of desalted water into the primary circuit subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary circuit subsystem until the temperature regulating rod reaches the safety position, comprising: Calculating the target amount of deionized water required for diluting boric acid with deionized water according to the middle position of the temperature adjustment rod, the preset safety position and the preset initial boric acid concentration of the primary circuit subsystem; Dividing the target desalted water volume required to dilute the boric acid with the desalted water into a plurality of sub-water volumes; The desalted water of each sub-water volume is controlled to be injected into the primary subsystem according to a second preset time period, so as to adjust the position of the temperature regulating rod by diluting the boric acid in the primary subsystem in batches until the temperature regulating rod reaches the safe position.

7. The method according to any one of claims 1 to 6, characterized in that: In the step of calculating the target amount of desalted water required for diluting boric acid with desalted water according to the middle position of the temperature regulating rod, the preset safety position, and the preset initial boric acid concentration of the primary subsystem, injecting the target amount of desalted water into the primary subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary subsystem until the temperature regulating rod reaches the safety position, the method further comprises: Acquire a first preset position and a second preset position; wherein the first preset position is the maximum value of the preset safety adjustment band of the temperature adjustment rod, and the second preset position is the minimum value of the preset safety adjustment band of the temperature adjustment rod; Obtaining the lower limit position of the temperature regulating rod in the reactor; The safety position is determined according to the first preset position, the second preset position and the lower limit position, wherein the safety position is lower than the first preset position, and the safety position is higher than the second preset position, and the safety position is higher than the lower limit position.

8. The method according to any one of claims 1 to 6, characterized in that: The step of obtaining a second initial position of the temperature regulating rod in the reactor and numerically adjusting the initial correction factor according to the second initial position to obtain a target correction factor includes: Integrate and calculate the initial correction factor and the preset increment in a first preset time period to obtain a candidate correction factor; If the second initial position remains unchanged or increases, then in the next first preset time period, the candidate correction factor and the preset increment are integrated and calculated to obtain an intermediate correction factor, and the candidate correction factor is replaced by the intermediate correction factor; If the second initial position decreases, the candidate correction factor is used as the target correction factor.

9. The method according to any one of claims 1 to 6, characterized in that: The primary circuit subsystem includes a plurality of thermal circuits; before the temperature regulating rod is controlled to move to the middle position according to the target correction factor, the target power, the measured temperature of the primary circuit subsystem, and the measured power of the reactor, the measured temperature of the primary circuit subsystem is obtained by the following steps: For each of the thermal circuits, obtaining an inlet temperature of the thermal circuit and an outlet temperature of the thermal circuit; Performing mean calculation based on the inlet temperature and the outlet temperature to obtain an average temperature; The average temperature is screened to obtain the measured temperature of the primary circuit subsystem.

10. An electronic device, characterized in that: The electronic device comprises a memory and a processor, the memory stores a computer program, and the processor implements the method according to any one of claims 1 to 9 when executing the computer program.

11. A nuclear power plant system, characterized in that: The nuclear power plant system comprises: The electronic device as claimed in claim 10; A power regulating rod, a temperature regulating rod, a primary circuit subsystem and a secondary circuit subsystem, wherein the primary circuit subsystem includes a reactor.

12. An adjusting rod control device, characterized in that: The device comprises: An operating condition information acquisition module, used to acquire the operating condition information of the nuclear power plant system; a target power acquisition module, configured to acquire a target power of the reactor matching the load shedding condition in response to the operating condition information being a load shedding condition; A load demand signal acquisition module, used to determine the secondary circuit load demand signal of the secondary circuit subsystem according to the target power and a preset initial correction factor; a first rod position control module, used for controlling the movement of the power regulating rod according to the secondary circuit load demand signal and the first initial position of the power regulating rod in the reactor to adjust the power of the reactor to the target power; a correction factor adjustment module, used for obtaining a second initial position of the temperature adjustment rod in the reactor, and numerically adjusting the initial correction factor according to the second initial position to obtain a target correction factor; a second rod position control module, used for controlling the temperature regulating rod to move to an intermediate position according to the target correction factor, the target power, the measured temperature of the primary circuit subsystem, and the measured power of the reactor; The dilution adjustment module is used to calculate the target amount of desalted water required to dilute the boric acid based on the middle position of the temperature adjustment rod, the preset safety position and the preset initial boric acid concentration of the first-loop subsystem, and inject the desalted water of the target amount of desalted water into the first-loop subsystem to adjust the position of the temperature adjustment rod by diluting the boric acid in the first-loop subsystem until the temperature adjustment rod reaches the safety position.

13. A computer-readable storage medium storing a computer program, characterized in that: When the computer program is executed by a processor, the method according to any one of claims 1 to 9 is implemented.

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